Alternatives and similar repositories for msr-archive

Users that are interested in msr-archive are comparing it to the libraries listed below

• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 6 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated last month
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆53Updated this week
• ezsolti / RFP
  ☆33Updated 5 months ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆21Updated last week
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated last week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated 3 weeks ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆18Updated last week
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 2 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated 2 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆122Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated last week
• Open-Sn / opensn
  Open-source Sn software
  ☆52Updated last week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last week
• llnl / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆32Updated last month
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated this week
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• Ahmed-Naceur / dragon5
  Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code
  ☆11Updated 3 years ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 6 months ago
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆21Updated 5 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆54Updated 2 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated this week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 5 months ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 7 months ago
• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆171Updated last week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year